束流瞬变下Ci ADS次临界反应堆燃料包壳安全分析  

Safety Analysis of CiADS Sub-Critical Reactor Fuel Cladding under Beam Transients

作　　者：张庆阳 顾龙[1,2] 彭天骥 盛鑫 Zhang Qingyang;Gu Long;Peng Tianji;Sheng Xin(Institute of Modem Physics,Chinese Academy of Sciences,Lanzhou,730030,China;University of Chinese Academy of Sciences,Beijing,100043,China)

机构地区：[1]中国科学院近代物理研究所,兰州730030 [2]中国科学院大学,北京100043

出　　处：《核动力工程》2018年第5期51-57,共7页Nuclear Power Engineering

基　　金：国家自然科学基金资助项目(11705255);中国科学院"西部之光"人才培养引进计划资助项目(29Y728010)

摘　　要：利用反应堆系统分析程序RELAP5mod4.0模拟了加速器驱动嬗变研究装置(Ci ADS)次临界反应堆燃料棒在发生失束事件时的响应特性;利用有限元软件ANSYS 17.0计算了CiADS次临界反应堆燃料包壳在失束事件下的疲劳寿命;预测了中国未来百兆瓦级加速器驱动次临界系统(ADS)中燃料包壳的疲劳寿命。研究表明:失束时CiADS次临界反应堆功率瞬间下降到满功率的2.156%;失束事件下CiADS次临界反应堆的燃料包壳的疲劳寿命在108次以上;失束事件不会对中国未来百兆瓦级ADS中的燃料包壳造成疲劳损伤。The response characteristics of the fuel rods in the sub-critical reactor of China Initiative Accelerator Driven System（CiADS） under beam trip were simulated by the reactor system analysis program RELAP5 mod4.0. The fatigue life of the fuel cladding in CiADS under beam trip is calculated by ANSYS 17.0. The fatigue life of the fuel cladding in hundred megawatt Accelerator Driven Sub-critical System（ADS） to be designed in China is predicted. The results show that the power of Ci ADS subcritical reactor instantaneously falls to 2.156% of full power when beam trip lost. The fatigue life of the fuel cladding of the CiADS subcritical reactor under beam trip is above 108. the beam trip will not cause fatigue damage to fuel cladding in hundred megawatt ADS to be designed in China.

关 键 词：加速器驱动嬗变研究装置(CiADS) 失束 应力分析 疲劳寿命 

分 类 号：TL364[核科学技术—核技术及应用]